• 제목/요약/키워드: Control rod drive mechanism(CRDM)

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Study on Rod Position Indication System using Permanent Magnets with Shielding Plates for a Control Rod Drive Mechanism

  • Lee, Jae Seon;Cho, Sang Soon;Kim, Jong Wook
    • Journal of Magnetics
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    • 제20권4호
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    • pp.439-443
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    • 2015
  • A control rod drive mechanism (CRDM) is an electromechanical equipment that provides linear movement for the control rods to control the nuclear reactivity in a nuclear reactor. A rod position indication system (RPIS) detects the control rod's position. To enhance the measurement accuracy of the system, a magnetostrictive type sensor with capability of generating operation limiting signals would be adapted instead of a conventional RPIS for a CRDM. An RPIS was modelled for a numerical analysis with the permanent magnets at the stationary limit positions and magnetic shielding plates with a moving permanent magnet. The performance analysis of the RPIS were conducted, and the results were discussed here.

Closed-Loop Timing Controller Design for Control Rod Drive Mechanism (CRDM) Control System in Pressurized Water Reactor

  • Kim, Byeong-Moon;Joon Lyou
    • Nuclear Engineering and Technology
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    • 제29권2호
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    • pp.167-174
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    • 1997
  • The method that the operating condition of Control Rod Drive Mechanism (CRDM) can be monitored without mounting sensors within CRDM housing was developed, and by using this developed method the closed-loop controller for the CRDM was designed which can optimize the performance and maximize the reliability of CRDM operation. Neural network is utilized as pattern recognition engine in detecting CRDM actuation. In this paper, most problems in previous open loop system are resolved. The control algorithms for closed-loop system ore developed and implemented within the hardware of timing controller based on microprocessor. All functions in the timing controller ore verified by means of real time CRDM simulator. The results show that the timing controller performs its intended functions properly.

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기계적 물성 변이를 고려한 원자로 압력용기(RPV : reactor pressure vessel) 상부 제어봉 구동 장치(CRDM : control of rod diver mechanism) 관통 노즐 이종재 용접부의 균열해석 (Crack analysis of mis-matched welding at CRDM(control rod drive mechanism) upper penetration nozzles of RPV(reactor pressure vessel) considering the change of mechanical properties)

  • 이용우;김종성;이강용
    • 대한용접접합학회:학술대회논문집
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    • 대한용접접합학회 2005년도 춘계학술발표대회 개요집
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    • pp.241-243
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    • 2005
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Development of A Test Apparatus for Control Rod Drive Mechanism in Nuclear Power Plants

  • Kim, Choon-Kyung;Cheon, Jong-Min;Lee, Jong-Moo;Kim, Seog-Joo;Kwon, Soon-Man
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2003년도 ICCAS
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    • pp.1732-1735
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    • 2003
  • In this paper, a DSP-based test apparatus for Control Rod Drive Mechanism (CRDM) that is used in nuclear power plants is described. Using this apparatus, we can test the mechanical and electrical characteristics of CRDM and obtain some information about how to improve the CRDM further and how to design a power controller to actuate the CRDM. Since firing angles can be directly applied to the gate-drive circuits of thyristors in the power controller by using this apparatus, the maximum and minimum values of firing angles within available limits are easily measured. Also step-current inputs help us investigate each coil's response characteristics. Therefore, we can easily find the range of control gains which enables a stable CRDM operation in insertion and withdrawal actions at high speed, mid speed, and low speed. Since this apparatus has a test mode in which an insertion or withdrawal action is divided into several phases so that the current command for each phase is given step by step, we may judge whether the CRDM works as expected or not. We also describe a fault detection capability of the test apparatus for the power controller by using discrete Fourier transform.

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JRTR 제어봉구동장치의 내진시험 (Seismic Test of the Control Rod Drive Mechanism for JRTR)

  • 최명환;김경호;선종오;조영갑
    • 한국소음진동공학회논문집
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    • 제26권5호
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    • pp.552-558
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    • 2016
  • A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod within a reactor core to control the reactivity of the core. The CRDM for Jordan Research and Training Reactor with 5MW power has been designed and fabricated based on the HANARO’s experience through KAERI and DAEWOO consortium. This paper describes the seismic test results to demonstrate the operability, the drop performance and the structural integrity of CRDM during or after seismic excitations. The seismic tests are carried out under 5 OBE and 1 SSE loads at three Test Rigs simulating the reactor structure and the pool top. From the tests, the CRDM is smoothly driven without a malfunction of stepping motor under OBE load. The pure drop time under OBE and SSE loads is measured as 1.169s and 1.855s to meet the design requirement. Also, it is found that the CRDM maintains the structural integrity without a change of the function and natural frequency before and after seismic loads.

원자로 제어봉구동장치의 동작 검출을 통한 안전한 이중유지 방법 (The Method of safe double holding by detecting movements of Control Rod Drive Mechanism)

  • 천종민;김춘경;이종무;박민국;권순만
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2005년도 제36회 하계학술대회 논문집 D
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    • pp.2655-2657
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    • 2005
  • When a fault relating to the urgent alarm occurs, we must prevent control rods from dropping and make one of two grippers in Control Rod Drive Mechanism (CRDM) grip the drive rod taking a control rod assembly. To enhance the reliability of holding control rods, we order two grippers to hold the drive rod. This action is called the double holding. In the middle of the movement of the drive rod, the latching of the drive rod can cause friction between a gripper and the drive rod. This state may give damage to both the gripper and the drive rod. In this paper, we have devised the method which can have two grippers hold the drive rod more stably, without damaging the equipment.

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원자로 제어봉구동장치의 안정적 제어봉 이중 유지 방법 (Stable Control-rod Double Hold Method of Control Rod Drive Mechanism)

  • 천종민;김춘경;이종무;정순현;김석주;권순만
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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    • pp.555-558
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    • 2003
  • When a fault relating to the urgent alarm occurs, we must prevent control rods from dropping and make one of two grippers in Control Rod Drive Mechanism (CRDM) grip the drive rod laking a control rod assembly. If a gripper with any problem is ordered to grip the drive rod, the gripper which cannot latch the rod stably will fail to take the rod. On the purpose of escaping this bad case, we order two grippers to hold the drive rod and enhance the reliability of holding control rods. This action is called the double hold. In the middle of the movement of the drive rod, the latching of the drive rod can cause friction between a gripper and the drive rod. This state may give damage to both the gripper and the drive rod. In this paper, we have devised the method which can have two grippers hold the drive rod more stably, without damaging the equipment.

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Analysis and optimization research on latch life of control rod drive mechanism based on approximate model

  • Ling, Sitong;Li, Wenqiang;Yu, Tianda;Deng, Qiang;Fu, Guozhong
    • Nuclear Engineering and Technology
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    • 제53권12호
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    • pp.4166-4178
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    • 2021
  • The Control Rod Drive Mechanism (CRDM) is an essential part of the reactor, which realizes the start-stop and power adjustment of the reactor by lifting and lowering the control rod assembly. As a moving part in CRDM, the latch directly contacts with the control rod assembly, and the life of latch is closely related to the service life of the reactor. In this paper, the relationship between the life of the latch and the step stress, friction stress, and impact stress in the process of movement is analyzed, and the optimization methodology and process of latch life based on the approximate model are proposed. The design variables that affect the life of the latch are studied through the experimental design, and the optimization objective of design variables based on the latch life is established. Based on this, an approximate model of the life of the latch is built, and the multi-objective optimization of the life of the latch is optimized through the NSGA-II algorithm.

원자로 제어봉 구동장치 제어시스템용 전력제어기 개발 (Development of Power Controller for Control Rod Drive Mechanism in Reactor)

  • 김춘경;천종민;이종무;권순만
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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    • pp.575-579
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    • 2003
  • In this paper, we describe a Duplex Power Controller for Control Rod Control System(CRCS). A Duplex Power Controller has the various functions for the reliable operations of Control Rod Drive Mechanism(CRDM). Also we have implemented the diverse functions by utilizing the developed Duplex Power Controller. Due to the developed Duplex Power Controller, we are assured that the commercial operation by this system be made before long.

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$H_\infty$ 필터를 이용한 원자력발전소 제어봉구동장치의 고장 검출 (A Fault Detection Method for Control Rod Drive Mechanisms in Nuclear Power Plants via $H_\infty$ Filtering)

  • 김석주;김춘경;이종무;권순만;박민국
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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    • pp.571-574
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    • 2003
  • This paper proposes a detection method for mechanically stuck control rod drive mechanism (CRDM) faults. During the normal operation of a CRDM, disturbance voltage is induced due to the change of the airgap flux between the stator and the armature of a CRDM. This disturbance voltage is estimated by using $H_\infty$ filtering method, and generalized plant is used in linear fractional transform (LFT) framework. $H_\infty$ filtering is described and solved in terms of linear matrix inequalities (LMIs). Simulation results are shown.

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